Author: David Bruce Fossan
Publisher:
ISBN:
Category : Beryllium
Languages : en
Pages : 178
Book Description
Fast-neutron Total Cross Sections of Beryllium, Carbon, and Oxygen
Author: David Bruce Fossan
Publisher:
ISBN:
Category : Beryllium
Languages : en
Pages : 178
Book Description
Publisher:
ISBN:
Category : Beryllium
Languages : en
Pages : 178
Book Description
The Total Scattering Cross-sections of Deuterium and Oxygen for Fast Neutrons
Author: Richard G. Nucholls
Publisher:
ISBN:
Category : Deuterium
Languages : en
Pages : 12
Book Description
Publisher:
ISBN:
Category : Deuterium
Languages : en
Pages : 12
Book Description
Legendre Expansion Coefficients for the Angular Distribution of Elastically Scattered Neutrons and Fast-neutron Cross Sections for Deuterium, Geryllium, Carbon, Oxygen, Zirconium, Lead, and Bismuth
Author: G. D. Joanou
Publisher:
ISBN:
Category : Beryllium
Languages : en
Pages : 84
Book Description
Publisher:
ISBN:
Category : Beryllium
Languages : en
Pages : 84
Book Description
Neutron Cross Sections of Nitrogen, Oxygen, Aluminum, Silicon, Iron, Deuterium, and Beryllium
Author: J. H. RAY
Publisher:
ISBN:
Category :
Languages : en
Pages : 181
Book Description
Neutron cross-section sets were prepared for N, O, Al, Si, Fe, D, and Be for neutron energies from 0.037 eV to 18 MeV. The cross sections tabulated include the total, elastic, inelastic, (n,2n), and cross sections for charged particle emission. Information is also given on the angular distribution of elastically scattered neutrons and on the energy distribution of neutrons and gamma-rays following nonelastic reactions. (Author).
Publisher:
ISBN:
Category :
Languages : en
Pages : 181
Book Description
Neutron cross-section sets were prepared for N, O, Al, Si, Fe, D, and Be for neutron energies from 0.037 eV to 18 MeV. The cross sections tabulated include the total, elastic, inelastic, (n,2n), and cross sections for charged particle emission. Information is also given on the angular distribution of elastically scattered neutrons and on the energy distribution of neutrons and gamma-rays following nonelastic reactions. (Author).
Neutron Cross Sections and Technology
Author: David T. Goldman
Publisher:
ISBN:
Category : Neutron cross sections
Languages : en
Pages : 674
Book Description
Publisher:
ISBN:
Category : Neutron cross sections
Languages : en
Pages : 674
Book Description
Neutron Cross Sections
Author: Donald J. Hughes
Publisher: Elsevier
ISBN: 1483282759
Category : Science
Languages : en
Pages : 193
Book Description
Neutron Cross Sections presents the principles of cross-section measurement and use, as well as sufficient theory so that the general behavior of cross sections is made understandable. This compilation is a direct result of experiences connected with the collection and evaluation of cross-section data during the past eight years at ""Sigma Centre"", Brookhaven National Laboratory. Here, experimental results received from laboratories throughout the world are carefully evaluated and compiled in the curves and tables of the large volume Neutron Cross Sections, The most recent version of the compilation, known as BNL 325, appeared 1 July 1955, and Supplement 1 to BNL 325 was published on 1 January 1957. The compilation itself consists almost completely of cross sections at specific energies, shown in the form of curves or tables, with only brief explanatory texts. The text opens with discussions of the general properties of cross sections and principles of nuclear structure that are important to the understanding of cross-section behavior. Separate chapters follow that describe specific techniques for measuring cross sections along with experimental results involving fast neutrons, resonance neutrons, resonances in fissionable materials, and thermal neutrons.
Publisher: Elsevier
ISBN: 1483282759
Category : Science
Languages : en
Pages : 193
Book Description
Neutron Cross Sections presents the principles of cross-section measurement and use, as well as sufficient theory so that the general behavior of cross sections is made understandable. This compilation is a direct result of experiences connected with the collection and evaluation of cross-section data during the past eight years at ""Sigma Centre"", Brookhaven National Laboratory. Here, experimental results received from laboratories throughout the world are carefully evaluated and compiled in the curves and tables of the large volume Neutron Cross Sections, The most recent version of the compilation, known as BNL 325, appeared 1 July 1955, and Supplement 1 to BNL 325 was published on 1 January 1957. The compilation itself consists almost completely of cross sections at specific energies, shown in the form of curves or tables, with only brief explanatory texts. The text opens with discussions of the general properties of cross sections and principles of nuclear structure that are important to the understanding of cross-section behavior. Separate chapters follow that describe specific techniques for measuring cross sections along with experimental results involving fast neutrons, resonance neutrons, resonances in fissionable materials, and thermal neutrons.
Collision Cross Sections of Carbon and Hydrogen for Fast Neutrons
Author: William Warner Sleator
Publisher:
ISBN:
Category : Collisions (Nuclear physics)
Languages : en
Pages : 24
Book Description
Publisher:
ISBN:
Category : Collisions (Nuclear physics)
Languages : en
Pages : 24
Book Description
Evaluations of the Fast Neutron Cross Sections of 52Cr and 56Fe Including Complete Covariance Information
Author: V. Pronyaev
Publisher:
ISBN:
Category : Neutron cross sections
Languages : en
Pages : 112
Book Description
Publisher:
ISBN:
Category : Neutron cross sections
Languages : en
Pages : 112
Book Description
FAST NEUTRON CROSS-SECTIONS OF ALUMINUM, SODIUM AND BERYLLIUM..
Author: JI-PENG CHIEN
Publisher:
ISBN:
Category :
Languages : en
Pages : 115
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 115
Book Description
Nuclear Cross Sections for 95-Mev Neutrons
Author: James DeJuren
Publisher:
ISBN:
Category : Bismuth
Languages : en
Pages : 24
Book Description
The total cross sections of twelve different elements were measured using the neutron beam from the 184-in. cyclotron, operating with deuterons. Bismuth fission ionization chambers were employed as both monitor and detector in conventional 'good geometry' attenuation measurements in the neutron flux emerging from the 3-in. diameter collimating port in the 10-ft-thick concrete shielding. The mean energy of detection of the neutrons in this experiment is estimated to be 95 Mev. Measurements were also made with a monitor and detector placed inside the concrete shielding where an intense neutron flux over a large area could be obtained. Attenuators of four different elements were placed in front of the detector in a 'poor geometry' arrangement so that attenuation was due essentially to inelastic collisions which degrade the neutron energy below the fission threshold. A second detector was placed outside the concrete shielding In the collimated neutron beam in line with the neutron source, absorber, and first detector. Attenuation in it is caused by both inelastic and elastic scattering. By this arrangement the ratio of inelastic to total cross section can be determined directly in one experiment. The nuclear radii as calculated from the observed cross section, using the theory of the transparent nucleus, vary as 1.38 x 10(exp-13) A(exp(1/3)) cm. In this energy range the ratios of the inelastic to total cross sections are all less than one-half.
Publisher:
ISBN:
Category : Bismuth
Languages : en
Pages : 24
Book Description
The total cross sections of twelve different elements were measured using the neutron beam from the 184-in. cyclotron, operating with deuterons. Bismuth fission ionization chambers were employed as both monitor and detector in conventional 'good geometry' attenuation measurements in the neutron flux emerging from the 3-in. diameter collimating port in the 10-ft-thick concrete shielding. The mean energy of detection of the neutrons in this experiment is estimated to be 95 Mev. Measurements were also made with a monitor and detector placed inside the concrete shielding where an intense neutron flux over a large area could be obtained. Attenuators of four different elements were placed in front of the detector in a 'poor geometry' arrangement so that attenuation was due essentially to inelastic collisions which degrade the neutron energy below the fission threshold. A second detector was placed outside the concrete shielding In the collimated neutron beam in line with the neutron source, absorber, and first detector. Attenuation in it is caused by both inelastic and elastic scattering. By this arrangement the ratio of inelastic to total cross section can be determined directly in one experiment. The nuclear radii as calculated from the observed cross section, using the theory of the transparent nucleus, vary as 1.38 x 10(exp-13) A(exp(1/3)) cm. In this energy range the ratios of the inelastic to total cross sections are all less than one-half.